A simulated high-temperature gas-cooled reactor (HTGR) helium environment was used to study the effects of surface finish conditions on the subsequent elevated-temperature corrosion behavior of key candidate structural materials. The environment contained helium with 500 ..mu..atm H/sub 2//50 ..mu..atm CO/50 ..mu..atm CH/sub 4//<0.5 ..mu..atm H/sub 2/O at 900/sup 0/C with total test exposure durations of 3000 hours. Specimens with lapped, grit-blasted, pickled, and preoxidized surface conditions were studied. Materials tested included two cast superalloys, IN 100 and IN 713LC; one centrifugally cast high-temperature alloy, HK 40 one oxice-dispersion-strengthened alloy, Inconel MA 754; and three wrought high-temperature alloys, Hastelloy All...
International audienceChromium-rich nickel base alloys 617 and 230 are promising candidate materials...
The current study was an attempt to evaluate the high cycle fatigue strength of Incoloy 800H in a Hi...
International audienceNickel base alloys Haynes 230 and Inconel 617 are of interest for gas cooled r...
In the High-temperature Gas-cooled Reactor (HTGR), structural metals will be required to operate at ...
International audienceNi-Cr-W alloys are claimed to present high creep strength, a good hot workabil...
The corrosion issues in high temperature reactors (HTRs) are probably less critical compared to such...
The helium coolant in the primary circuit of the high-temperature gas-cooled reactor (HTGR) contains...
International audienceHigh temperature corrosion properties of Haynes 230 were investigated in a pur...
To study the corrosion mechanisms in the complex gas-metal systems of high temperature reactor (HTR)...
The helium coolant in high-temperature reactors inevitably contains low levels of impurities during ...
International audienceThe corrosion behavior in impure helium of Haynes 230, a nickel base alloy can...
Within the national and international research program of materials for advanced nuclear reactors Cz...
The high temperature gas-cooled reactor (HTGR) design has been selected for the Next Generation Nucl...
This project aims to understand the processes by which candidate materials degrade in He and supercr...
International audienceChromium-rich nickel base alloys 617 and 230 are promising candidate materials...
The current study was an attempt to evaluate the high cycle fatigue strength of Incoloy 800H in a Hi...
International audienceNickel base alloys Haynes 230 and Inconel 617 are of interest for gas cooled r...
In the High-temperature Gas-cooled Reactor (HTGR), structural metals will be required to operate at ...
International audienceNi-Cr-W alloys are claimed to present high creep strength, a good hot workabil...
The corrosion issues in high temperature reactors (HTRs) are probably less critical compared to such...
The helium coolant in the primary circuit of the high-temperature gas-cooled reactor (HTGR) contains...
International audienceHigh temperature corrosion properties of Haynes 230 were investigated in a pur...
To study the corrosion mechanisms in the complex gas-metal systems of high temperature reactor (HTR)...
The helium coolant in high-temperature reactors inevitably contains low levels of impurities during ...
International audienceThe corrosion behavior in impure helium of Haynes 230, a nickel base alloy can...
Within the national and international research program of materials for advanced nuclear reactors Cz...
The high temperature gas-cooled reactor (HTGR) design has been selected for the Next Generation Nucl...
This project aims to understand the processes by which candidate materials degrade in He and supercr...
International audienceChromium-rich nickel base alloys 617 and 230 are promising candidate materials...
The current study was an attempt to evaluate the high cycle fatigue strength of Incoloy 800H in a Hi...
International audienceNickel base alloys Haynes 230 and Inconel 617 are of interest for gas cooled r...